DETERMINATION OF TRITIUM IN VEGETATION IN THE OBSERVATION AREA OF REACTOR WWR-K IN KAZAKHSTAN

M.V. Krasnopyorova, M.A. Severinenko, P.V. Kharkin, O.S. Milts, V.A. Makarova, Zh.K. Sanalbay
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Abstract

In assessing the impact of radiation-hazardous facilities on the environment and humans, considerable attention is currently paid to the problem of tritium and its compounds intake. It is important to note that to date there are no effective industrial technologies for efficient capture of this radionuclide. As a result, all the tritium produced during the operation of nuclear power plants with emissions and discharges is released into the environment. This leads to increased tritium concentrations in the environment, including vegetation. The aim of this work is to develop and adapt a set of methods for sample preparation and determination of tritium in vegetation samples. Methodology: A special Carbolite Gero MTT tube furnace was used to improve sample preparation methods and maximise the recovery of organically bound tritium from vegetation. Tritium was measured by liquid scintillation beta spectrometry. Results and Discussion: This research paper presents the results of the study and implementation of the method of tritium determination in vegetation near the VVR-K reactor located in the city of Almaty, Kazakhstan. Conclusions: The developed method of tritium determination in vegetation can be applied for radiation monitoring of tritium content and its compounds in the vicinity of nuclear industrial facilities. The presented data emphasise the need for systematic studies of tritium accumulation in environmental components. It is expected that in the future, using the implemented method, the studied area will be studied in detail, taking into account an extended set of factors: meteorological conditions, reactor operation mode and others. Thus, for a more complete and reliable assessment of tritium radionuclide activity determination, it is necessary to carry out works to determine the type of vegetation accumulating this isotope.
哈萨克斯坦wwrk反应堆观测区植被中氚的测定
在评估辐射危险设施对环境和人类的影响时,目前相当重视氚及其化合物摄入的问题。必须指出的是,迄今为止还没有有效的工业技术来有效地捕获这种放射性核素。因此,核电站在运行过程中产生的所有氚都被排放到环境中。这导致环境中的氚浓度增加,包括植被。本工作的目的是发展和适应一套样品制备和测定植被样品中的氚的方法。方法:采用一种特殊的Carbolite Gero MTT管式炉改进样品制备方法,最大限度地从植被中回收有机结合的氚。氚用液体闪烁-光谱法测定。结果与讨论:本文介绍了位于哈萨克斯坦阿拉木图市VVR-K反应堆附近植被中氚测定方法的研究和实施结果。结论:所建立的植被氚测定方法可用于核工业设施周边地区氚及其化合物的辐射监测。目前的数据强调需要系统地研究氚在环境成分中的积累。预计在未来,使用实施的方法,将对研究区域进行详细研究,考虑到一组扩展的因素:气象条件,反应堆运行模式等。因此,为了更完整、可靠地评估氚放射性核素活度测定,有必要开展富集该同位素的植被类型确定工作。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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